The design of nuclear pressure vessel requires the description of various dynamic effects, among which fluid-structure interaction. The present paper gives on overview of DCNS R&D methodology for fluid-structure interaction modelling in nuclear pressure vessels: a global R&D program has been launched by DCNS within a collaborative framework, or the application of numerical methods in FSI to the dynamic analysis of nuclear propulsion systems (nuclear reactors and steam generators). Two applications are proposed in the paper as a conclusive example of this R&D program. 1) The dynamic analysis of a nuclear reactor with FSI is made possible by the implementation of the so-called (u, p, φ) formulation within the ANSYS code [J.F. Sigrist, S. Garreau, Dynamic Analysis of Fluid-Structure Interaction Problems with Spectral Method Using Pressure-Based Finite Elements, Finite Element Analysis in Design, 43 (4), 287–300, 2007] allowing the application of modal methods in the context of coupled fluid-structure systems; importance of FSI in the dynamic behaviour of a nuclear reactor are underlined by a fully coupled analysis. 2) The dynamic analysis of a steam generator with FSI is made possible by the implementation of an homogenisation technique within the CASTEM code [J.F. Sigrist, D. Broc, Dynamic Analysis of a Tube Bundle with Fluid-Structure Interaction Modelling Using a Homogenisation Method, Computer Methods in Applied Mechanics and Engineering, 197 (9–12), 1080–1099, 2008] allowing the description of the interactions between the confined fluid and inner structures and tube bundle in a straightforward manner.

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